Publications by Stefan Radman | EPFL Graph Search

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The present article describes the preliminary design studies for an oncoming experimental programme at the CROCUS facility. CROCUS is a teaching and research zero-power reactor operated by the Laboratory for Reactor Physics and Systems Behaviour (LRS) at t ...

The analysis of nuclear reactors for performance and safety assessment benefits from the use of computational tools. In this context, this work aims at the development and application of a thermal-hydraulics methodology and related software that respond to ...

The GeN-Foam multi-physics code enables coupled thermal-hydraulic, neutronic, and thermal-mechanical analysis of fast reactor cores with 3-D unstructured deformable meshes. Advances within the Horizon2020 ESFR-SMART project, as well as trends towards highe ...

A porous medium-based representation of nuclear reactors and complex engineering systems more in general can significantly reduce simulation and modelling costs, while preserving a reasonable degree of accuracy via regime map-based correlations for modelli ...

The deterministic solution of the neutron transport problem entails the coupled solution of several partial differential equations, one for each energy group, direction and/or spherical harmonic. Several techniques have been devised for accelerating the so ...

Following the growing interest that we observe in the use of OpenFOAM for nuclear reactor analysis, the current work presents a point-kinetics model and associated open-source code that can easily be inte-grated in existing thermal-hydraulic solvers to str ...

Recent numerical advancements at the Laboratory for Reactor Physics and Systems Behaviour (LRS) have led to the development of a novel two-phase porous medium-based thermal-hydraulic simulation tool, integrated in the broader multi-physics framework of the ...

The current work presents a simplified benchmark for a pool-type Sodium Fast Reactor based on a 2D (r-z) geometry for testing tightly-coupled spatial neutron transport, thermal-hydraulics and thermal-mechanics modeling. The new benchmark is motivated by de ...

The OpenFOAM-based GeN-Foam solver has recently been extended to allow simulating water boiling based on a porous-medium approach. This paper describes such extension and preliminarily validates it based on the OECD/NRC PSBT benchmark. Three benchmark exer ...

Stefan Radman

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Design of Separated Element Reflector Experiments in CROCUS: PETALE

A Coarse-mesh Methodology for the Analysis of One and Two-phase Nuclear Reactor Thermal-hydraulics in a Multi-physics Context

A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design

Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM

A reduced order accelerator for time-dependent segregated neutronic solvers

Development of a point-kinetics model in OpenFOAM, integration in GeN-Foam, and validation against FFTF experimental data

Development of a novel two-phase flow solver for nuclear reactor analysis: Validation against sodium boiling experiments

A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors

Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark